Investigations on the flooding behaviour of a partially degraded reactor core

Ailine J. Trometer
This work investigates a mid-sized break loss of coolant accident (MBLOCA) with a 200 cm2 leak in the hot leg next to the pressurizer surge line in the most common reactor type which is the 1; 300MWel KONVOI class pressurized water reactor (PWR). The scope was to analyze different reflooding scenarios, where the reactor core has already started melting when the reflooding is initiated. For this scenario a basic simulation called „BaseCase“ is conducted to...
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